Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens
スポンサーリンク
概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 2012-05-01
著者
-
Kasada Ryuta
Institute Of Advanced Energy Kyoto University
-
Kimura Akihiko
Institute Of Advanced Energy Kyoto University
-
Kim Byung
Graduate School Of Energy Science Kyoto University
-
MITSUI Hideaki
Graduate School of Energy Science, Kyoto University
-
Mitsui Hideaki
Graduate School Of Energy Science Kyoto University
関連論文
- High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems : Nano-sized oxide dispersion strengthening steels
- Effects of Zr Addition on the Microstructure of 14%Cr4%Al ODS Ferritic Steels
- Amorphous Alloys with Nitride Particles Produced by a Nitrogen Plasma-Alloy Reaction : Condensed Matter
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Precipitation Behavior of Irradiated Reduced-Activation Ferritic Steels
- Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel
- Mechanical Behavior of Oxide Dispersion Strengthened Steels Irradiated in JOYO
- Application of Small Punch Test to Evaluate Sigma-Phase Embrittlement of Pressure Vessel Cladding Material
- Effects of Aluminum on the Corrosion Behavior of 16% Cr ODS Ferritic Steels in a Nitric Acid Solution
- Factors Controlling Irradiation Hardening of Iron-Copper Model Alloy
- Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens
- PREFACE
- Effects of Nickel Addition on Microstructural Evolution and Mechanical Properties of Reduced Activation Martensitic Steels Irradiated in the ATR-A1
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Structure-Activity Relationship of the Warburgia Sesquiterpene Dialdehydes
- Irradiation Effect on Tensile Property of F82H IEA and Its Joint in TITAN Project